ML20115J675

Proposed Rev 1 to Tech Spec Change Request 100,changing Section 3.5.A.8 Re Shock Suppressors,Section 4.5.Q Re Insp of Snubbers,Section 6.10.2 Re Record Retention of Snubber Svc Life & Deleting Table 3.5.1

ML20115J675
Person / Time
Site:	Oyster Creek
Issue date:	04/15/1985
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20115J656	List: ML20115J654 ML20115J675
References
NUDOCS 8504240067
Download: ML20115J675 (12)

Text

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3.5-3 ,

b. Two of the fourteen suppression chamber - drywell vacuum breakers may be inoperable provided that they are secured in the closed position.

c. One position alarm circuit for each operable vacuum breaker may be inoperable for up to 15 days provided that each operable sup-pression chamber - drywell vacuum breaker with one defective alarm circuit is physically verified to be closed inanediately and daily during this period.

6. After completion of the startup test program and demonstration of plant electrical output, the primary containment atmosphere shall be reduced to less than 5.0% 02 with nitrogen gas within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the reactor mode selector switch is placed in the run mode. Primary containment deinerting may consnence 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to a scheduled shutdown.

7. If specifications 3.5.A.l.a. b, c(1) and 3.5.A.2 through 3.5.A.5 cannot be met, reactor shutdown shall be initiated and the reactor shall be in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

8. Shock Suppressors (Snubbers)

a. During all modes of operation except cold shutdown and refuel, all safety related snubbers shall be operable except as noted in l 3.5.A.8.b, c and d below.

b. With one or more snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber (s) to operable status.

c. If the requirements of 3.5.A.8.a and 3.5.A.8.b cannot be met, an orderly shutdown shall be initiated and the reactor shall be in a cold shutdown condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

'd. If a snubber is determined to be inoperable while the reactor is in the shutdown or refuel mode, the snubber shall be made operable or replaced prior to reactor startup.

9. Drywell-Suppression Chamber Differential Pressure I

a. Differential-pressure between the drywell and suppression chamber shall be maintained within the acceptable operating range shown

. on Figure 3.5-1 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the reactor mode selector switch is placed in the run mode. The differential pressure may be reduced to less than the range shown on Figure 3.5-1 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to a scheduled shutdown. The differential pressure may be decreased to less than the required value for a maximum of four hours during required operability testing of the drywell-pressure suppression chamber vacuum breakers.

Amendment No. 21, 25, 32

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8504240067 850415 PDR ADOCK 05000219 P PDR

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3.5-5 i l

importantly, the accessibility of the valve lever arm and position reference external to the valve. The fail-safe feature of the alarm circuits assures operator attention if a line fault j occurs.

1 Conservative estimates of the hydrogen produced, consistent with

' the core cooling system'provided, show that the hydrogen air i

' mixture resulting from a loss-of-coolant accident is considerably below the fimunability limit and hence it cannot burn, and '

inerting would not be needed. However, inerting of the primary

containment was included in the proposed design and operation.

' l The 5% oxygen limit is the oxygen concentration limit stated by >

the American Gas Association for hydrogen-oxygen mixtures below ,

which combustion will not occur.(4) i To preclude the possibility of starting up the reactor and l

operating a long period of time with a significant leak in the l

primary near rated system, temperature leak checks and pressure. must be made whenshown It has been the system 19

/ 80(9 (gt)or r that an acceptable margin with respect to flammability exists without containment inerting. Inerting the primary containment provides additional margin to that already considered acceptable. Therefore, permitting access to the drywell for the purpose of leak checking would not reduce the margin of safety

! below that considered adequate and is judged prudent in terms of the added plant safety offered by the opportunity for leak inspection. The 24-hour time to provide inerting is judged to be a reasonable time to perform the operation and establish the

required 02 limit.

Snubbers are designed to prevent unrestrained pipe motion under dynamic loads as might occur during an earthquake or severe l transient, while allowing normal thermal motion during startup

, and shutdown. The consequence of an inoperable snubber is an increase in the probability of structural damage to piping as a result of a seismic or other event initiating dynamic loads. It

, is, therefore, required that all snubbers required to protect the primary coolant system or any other safety system or component be operable during reactor operation.

I All safety related snubbers are visually inspected for overall integrity and operability. The l L

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i j Amendment No. 75 f

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3.5-6 inspection will include verification of proper orientation, adequate hydraulic fluid level: and proper attachment of snubber to piping and structures.

Because snubber protection is required only during low probability events, a period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is allowed for repairs or replacements. In case a shutdown is required, the allowance of 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> to reach a cold shutdown condition will permit an orderly shutdown consistent with standard operating procedures. Since plant startup should not commence with knowingly defective safety related equipment, Specification 3.5.A.8.d prohibits startup with l inoperable snubbers.

Secondary containment (5) is designed to minimize any ground level release of radioactive materials which might result from a serious accident. The reactor building provides secondary containment during reactor operation when the drywell is sealed and in service and provides primary containment when the reactor is shutdown and the drywell is open, as during refueling. Because the secondary containment is an integral part of the overall containment system, it is required at all times that primary containment is required.

Moreover, secondary containment is required during fuel handling operations and whenever work is being performed on the reactor or its connected systems in the reactor building since their operation i could result in inadvertent release of radioactive material.

l Amendment No. 14, 18, 75 Corrected December 24, 1984  !

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3.5-8 Table 3.5-1 (Deleted) s

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3.5-9 , .,[

TABLE 3.5.2 CONTAINMENT ISOLATION VALVES' VALVE FUNCTION / VALVE DESIGNATION ISOLATION SIGNALS Main Steam Isolation Valves (NS03A, NS03B, NSO4A, NSO4B)- 1 Main Steam Condensate Drain Valves (V-1-106, V-1-107, V-1-110, V-1-111) 1 Reactor Building Closed Cooling Valves (V-5-147, V-5-166, V-5-167) 2 Instrument Air Valve (V-6-395) 1 Emergency Condenser Vent Valves (V-14-1, V-14-5, V-14-19, V-14-20) 1 Reactor Cleanup Valves (V-16-1, V-16-2, V-16-14. V-16-61) 3 Shutdown Cooling Valves (V-17-19, V-17-54) 3 Drywell Equipment Drain Tank Valves (V-22-1, V-22-2) 3 Drywell Sump Valves (V-22-28, V-22-29) 3 Drywell & Torus Atmosphere Control Valves (V-27-1, V-27-2', V-27-3, V-27-4, 3 V-28-17, V-28-18 V-23-21 V-23-22, V-28-47, V-23-13 V-23-14, V-23-15 V-23-16 V-23-17, V-23-18, v-23-19, V-23-20) ~

Reactor Recirculation Loop Sample Valves (V-24-29, V-24-30) 1 Torus to Reactor Building Vacuum Relief Valves (V-26-16 V-26-18) 3*

Traversing In-Core Probe System (Tip machine ball valve No. 1, No. 2, No. 3, No. 4) 3

1) Reactor Isolation Signals as shown in Table 3.1.1

2) Low-Low Reactor Water Level and High Drywell Pressure; or Low-Low-Low Reactor Water Level.

3) Primary Containment Isolation Signals as shown in Table'3.1.1

• Valves automatically reset to provide vacuum. relief Amendment No. 54

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13-60 REQUIRED DRYWELL TO TORUS DIFFERENTIAL PRESSURE l.4 -

G a,

L3 - ACCEPTABLE

• a OPERATING RANGE ~

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0.9 . . . . . . . . . . . .

3.0 3.4 3.8 4.1 4.8 5.0 5.4 DOWNCOMER SUSMERGENCE', FT.

FIGURE 3.5-l

• The actual acceptable range of downconer submergence is governed by the Technical Specifications limit on mar 4==

3.5.A.1). This actual acceptable and m44== water volume in the torus (see section range of downcomer submergence will not encompass the full range of downcomer submergence indicated in the figure above.

i AMENDMENT NO. 46 . - '

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4.5-6a P. Suppression Chamber Surveillance

1. At least once per day the suppression chamber water level and temperature and pressure suppression system pressure shall be checked.

2. A visual inspection of the suppression chamber interior, including water line regions, shall be made at each major refueling outa,ge.

3. Whenever heat from relief valve operation is being added to the suppression pool, the pool temperature shall be continually mcnitored and also observed until the heat addition is terminated.

4. Whenever operation of a relief valve is indicated and the suppression pool temperature reaches 160*F or above while the reactor primary coolant system pressure is greater than 180 psig, an external visual examination of the suppression chamber shall be made before resuming normal power operation.

5. Drywell-Suppression Chamber Differential Pressure

a. The pressure differential between the drywell and suppression chamber shall be recorded at least once per shift when the reactor containment is required to be inerted by Specification 3.5.A.9.a.

b. Instrumentation to measure the drywell to suppression chamber differential pressure and suppression chamber water level shall be calibrated once every 6 months.

Amendment No. 18, 32

I 4.5-6a-1 Q. Shock Suppressors (Snubbers)

1. Each snubber shall be demonstrated operable by performance of the fol-lowing inspection program.

a. Visual Inspections All snubbers shall be visually inspected in accordance with the fol-lowing sche 6:le:

No. Inoperable Snubbers Subsequent Visual Per Inspection Period Inspection Period 0 18 months + 25%

1 12 months T 25%

2 6 months T 25%

3,4 124 days 125%

5,6,7 62 days + 25%

8 or more 31 days 125%

The required inspection interval shall not be lengthened more than one step at a time. The snubbers may be categorized into two groups: those access-ible and those inaccessible during reactor operation. Each group may be inspected independently in accordance with the above schedule.

b. Visual Inspection Acceptance Criteria Visual inspections shall verify (1) that there are no visible indications of damage or impaired OPERABILITY, (2) attachments to the foundation or sup-porting structure are secure, and (3) in those locations where snubber move-ment can be manually induced without disconnecting the snubber, that the snubber has freedom of movement and is not frozen up. Snubbers which appear inoperable as a result of visual inspections may be determined OPERABLE for the purpose of establishing the next visual inspection interval, providing that the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers that may be generically suscept-ible; or the affected snubber is functionally tested in the as found condi-tion and determined OPERABLE per Specifications 4.5.Q.d or 4.5.Q.e, as ap-plicable,

c. Functional Tests At least once each refueling outage, a representative sample (10% of the total of each type of snubber in use in the plant) shall be functionally tested either in place or in a bench test. For each snubber that does not meet the functional test acceptance criteria of Specification 4.5.Q.d or 4.5.Q.e, an additional 10% of that type of snubber shall be functionally tested.

The representative sample selected for functional testing shall include the various configurations, operating environments and the range of size and capacity of snubbers. At least 25% of the snubbers in the representative sample shall include snubbers from the following three categories:

Amendment No. 18

4.5-6a-2

1. The first snubber away from each reactor vessel nozzle.

2. Snubbers within 5 feet of heavy equipment (valve, pump, motor, etc.).

3. Snubbers within 10 feet of the discharge from a safety relief valve.

s In addition to the regular sample, snubbers which failed the previous func-tional test shall be retested during the next test period. If a spare snub-ber has been installed in place of a failed snubber, then both the failed (if it is repaired and installed in another position) and the' spare snubber shall be retested.

d. Hydraulic Snubbers Functional Test Acceptance Criteria The hydraulic snubber functional test shall verify that:

1. Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression.

2. Snubber bleed, or release rate, where required, is within the speci-fied range in compression or tension. For snubbers specifically required to not displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.

e. Mechanical Snubbers Functional Test Acceptance Criteria The mechanical snubber functional test shall verify that:

1. The force that initiates free movement of the snubber rod in either tension or compression is less than the specified maximum drag force. Drag force shall not have increased more than 50% since the last functional test.

Amendment No.

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l 4.5-6a-3 l

2. Activation (restraining action) is achieved within the specified range  ;

of velocity or acceleration in both tension and compression.

3. Snubber release rate, where required, is within the specified range in compression or tension. For snubbers specifically required not to displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified. )

f. Snubber Service Life Monitoring A record of the service life of each snubber, the date at which the desig-nated service life commences and the installation and maintenance records on which the designated service life is based shall be maintained as required by Specification 6.10.2.1.

Concurrent with the first inservice visual inspection and at least once per 18 months thereafter, the installation and maintenance records for each snubber shall be reviewed to verify that the indicated service life has not been exceeded or will not be exceeded prior to the next scheduled snubber service life review. If the indicated service life will be exceeded prior '

to the next scheduled snubber service life review, the snubber service life shall be reevaluated or the snubber shall be replaced or reconditioned so as to extend its service life beyond the date of the next scheduled service life review. This reevaluation, replacement or reconditioning shall be in-  ;

dicated in the records.

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l Amendment No.

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4.5-9b of the system. Although this is basically a leak test, since the filters have charcoal of known efficiency and holding capacity for elemental iodine and/or methyl iodide, the test also gives an indication of the relative ef-ficiency of the installed system. The test procedure is an adaptation of

, test procedures developed at the Savannah River Laboratory which were des- ,

cribed in the Ninth AEC Air Cleaning Conference.* '

j High efficiency particulate filters are installed before and after the char-i coal filters to minimize potential release of particulates to the environ-4 ment and to prevent clogging of the iodine filters. An efficiency of 99% is

' adequate to retain particulates that may be released to the reactor building following an accident. This will be demonstrated by testing with 00P as i testing medium.

4 If laboratory tests for the adsorber_ material in one circuit of the Standby Gas Treatment System are' unacceptable, all adsorber material in that circuit ,

shall be replaced with adsorbent qualified according to Regulatory Guide i

1.52. Any HEPA filters found defective shall be replaced with those quali-fled with Regulatory Position C.3.d of Regulatory Guide 1.52.

4 The snubber inspection frequency is based upon maintaining a constant level j of snubber protection. Thus, the required inspection interval varies in-i versely with the observed snubber failures. The number of inoperable snub-i bers found during a required inspection determines the time interval for the l next required inspection. Inspections performed before that interval has

! elapsed may be used as a new reference point to determine the next inspec-1 tion. However, the results of such early inspections performed before the original required time interval has elapsed (nominal time less 25%) may not be used to lengthen the required inspection interval. Any inspection whose results require a shorter inspection interval will override the previous j schedule.

To further increase the assurance of snubber reliability, functional tests should be performed once each refueling cycle. These tests will include 4

stroking of the snubbers to verify proper piston movement, lock-up and i

bleed. Ten percent or ten snubbers, whichever is less, represents an ade-quate sample for such tests. Observed failures of these samples should re-quire testing of additional units.

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• D. R. Muhbaier, "In Place Nondestructive Leak Test for Iodine Adsorbers", Proceedings of the Ninth AEC Air Cleaning Conference, USAEC Report CONF-660904, 1966.

i l Amendment No. 18

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6.10.2 The following records shall be retained for the duration of the Facility Operating License:

a .- Record and drawing changes reflecting facility design modifica-tions made to systems and equipment described in the Final Safety Analysis Report.

b. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.

c. Records of facility radiation and contamination surveys.

d. Records of radiation exposure for all individuals entering radi-ation control areas.

e. Records of gaseous and liquid radioactive material-released to the environs.

f. Records of transient or operational cycles for those facility components designed for a limited number of transients or cycles.

g. Records of training and qualification for current members of the plant staff.

h. Records of inservice inspections performed pursuant to these technical specificatons. -

1. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR

. 50.59.

j. Records of reviews by the Independent Onsite Safety Review Group.

k. Records for Environmental Qualification which are covered under the provisions of paragraph 6.14.

1. Records of the service lives of all snubbers, including the date at which the service life comences, and associated installation and maintenance records.

6.10.3 Quality Assurance Records shall be retained as specified by the Quality Assurance Plan.

6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR 20 and shall be ap-proved, maintained and adhered to for all operations involving personnel radiation exposure.

6.12- (Deleted) 6-23 Amendment No. 69, 78